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1·The company's engineers continue to pump seawater into the reactor pressure vessel, in an effort to cool it.

为了冷却压力容器，这个公司的工程师持续地向它注入海水。

2·The powerful system has the capacity to propel thousands of gallons of water a minute throughout a reactor pressure vessel and storage pool.

这种强力的系统有能力在一分钟内驱动上千加仑的水流经反应堆的高压容器和储存池。

3·The study on flow and heat transfer in downcomer under loss of coolant accident (LOCA) is important to the safety of reactor pressure vessel (RPV).

失水事故工况(LOCA)下反应堆下降环腔内的流动和传热研究，对反应堆压力容器(RPV)的安全具有重要的意义。

4·One of the basic failures of reactor pressure vessel is the failure of flange sealing system, so it is very important to study the performance of its sealing system.

法兰密封失效是核压力容器的最基本失效形式之一，研究其密封性能具有十分重要的意义。

5·As the basic safe wall of nuclear reactor, the reactor pressure vessel not only bears high temperature and high pressure, but also contains radioactive working substance.

反应堆压力容器作为反应堆的基本安全屏障，承受高温、高压且内部包含具有放射性的工作介质。

6·In this paper, a solute drag model was proposed to predict the phosphorus inter granular segregation in reactor pressure vessel steels and compared with the rate theory model.

本文提出了预测核反应堆压力容器钢中杂质元素(主要是磷)晶间非平衡偏析的溶质拖拽模型，并且与速率理论模型进行了对比。

7·The improved transient sealing analysis program for reactor pressure vessel is applied to analyze the 1/4 structure of the model under the cool and the thermal work conditions.

应用改进后的反应堆压力容器瞬态密封分析程序对压力容器模拟体1/4模型进行了冷态和热态密封分析。

8·The reactor pressure vessel composed of spherical top and lower heads, upper and lower flanges, bolts, cylinder and two O-rings, as a static indeterminate system has been studied.

本文将反应堆压力壳的球顶盖、上下法兰、螺栓、筒体及双道O形环作为一个超静定系统进行了应力和变形分析。

9·Structural and mechanical design are performed according to the requirement on the overall design and design input for the reactor pressure vessel support of Qinshan Phase II NPP Project.

根据总体设计要求和设计输入要求，进行了秦山核电二期工程反应堆压力容器支承的结构设计和力学设计。

10·Neutron irradiation-induced phosphorus intergranular segregation in the reactor pressure vessel steels is the one of main reasons resulting in brittle fracture of the nuclear reactor vessel.

中子辐照引起的核反应堆压力容器钢中磷的晶间偏析是导致核反应堆压力容器脆性断裂的主要因素之一。